View source for 2CAN019108, Responds to 900830 Request for Addl Info Re 891019 Proposed Tech Spec Change for Insp Frequency of Spent Fuel Pool.Insp Procedure Encl

{{Adams
| number = ML20066F409
| issue date = 01/15/1991
| title = Responds to 900830 Request for Addl Info Re 891019 Proposed Tech Spec Change for Insp Frequency of Spent Fuel Pool.Insp Procedure Encl
| author name = Fisicaro J
| author affiliation = ENTERGY OPERATIONS, INC.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000368
| license number = 
| contact person = 
| document report number = 2CAN019108, 2CAN19108, NUDOCS 9101230313
| package number = ML20066F410
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 4
}}

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                                                                                                                                                             <l January 15, 1991                                                                                                                         l      '
I 2CAN019108                                                                                                                                j o
U. S. Nuclear Regulatory Commission                                                                                                          !
Document- Control: Desk -                                                                                                                -;
Hall Station P1-137'                                                                                                                      l Washington, DC 20555

==Subject:==
: Arkansas Nucionr ono - Unit 2 Docket 1Nos.50-]
License Nos. NPF- --
Rospo.. a:co Roquest for Additional Informat!lon1                                                                             ;
on Spont ~ Fuel-Pool Technical Specification Change Gentiomen:
In our letter of October = 19, 1989 (2CAN108903).. Proposed Technlent Specification Chango - Spent Fuel Pool Survo111ance Interval, Entergy Operations requestod an' amendmont to. the Arkansas yNucinar Ono.: Unit 2 Technical Specif1 cations for: inspection Irequency 'of tho' SpontL Ftial Pool.-
In your letter of August 30, 1990 I'~ a089004),-tho~. Staff; requested:
additional information_Jn ordoruto c rplete its;ovaluation.c Provided as an attachment to this. letter 18: our_responso-to-your request.-_ Also-wo-have-provided a. copy of.our current procedure for InspectionLof the;' Spent Fuol Pool to further assist you in- your ovaluntion.
Should you or your staf f havn questions regarding- this- responso, please do                       -
not hesitato to en11.
Very truly yours, I
James w .)SH
                                  ~
                                . Fislcnto
                     -Hanager, Licensing JJF/ CWT
                    ' Attachments 9101230313 910115
           . PDR         ADOCK 05000368 I                                                                                               -Ul A
1   P.                          PDR     3 (MJsua                                      ~
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: d. S. NRC
          . , ' Uonuary 15, 1991
              . Pago 2 cc:   Mr. Robert Martin U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000' l                      Arlington, TX 76011
{                      NRC Sonfor Resident Inspector Arkansas Nuclear One - ANO-1 & 2 Number 1, Nuclear Plant Road Russellville, AR 72801 Mr. Tom Alexion NRR Project Manager, Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Mall Stop-13-D                        One White Flint North 11555 Rockville Piko Rockville, Maryland 20852 Ms. Sheri Peterson NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory Commission-NRR Mail Stop 13-D-18 One Whito Flint North 11555 Rockvillo Pike Rockville, Maryland 20852 i
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                                      ' ATTACHMENT TO-20AN019108f
: 1. Relative-to your inspection of the fuel pool,; define what is considered to be a significant crack.
The inspection.and mapping ~ of deterioration in the spent fuel pool; concrete surface-is accomplished in-accordance with ANO Procedure 2306.010 (attached). The significance associated-with-a crack.is' dependent upon its size and an evaluation of-it's impact upon the-integrity of the spent fuel pool. This is discussed further in.
response to question    2.,
: 2. What factions are to be- takenL when- a -significant. crack is identified?c Procedure 2306.01 provides the _ following ' guidance with: respect' toithe inspection of,the-spent. fuel.poo F concrete-surface.-
A. All cracks greater-in widthithan 0.01" are measured and mapped.-
B. All crack- changes _o'r deficiencies: are evaluated - to determine -
it's impact upon spent fuel pool integrity'(Section 8.3;3 and 8.3.4 of procedure.2306.010).
C.. Any cracks which impact the fuel pool-integrity based upon the-Engineer's evaluation will require.that appropriate reportingL requirements'and corrective action be= initiated.-
: 3.   . What are the acceptance values for all~ recorded measurements? -
procedure 2306.010 requires that' changes'in crack patterns =be          .
evaluated'by-the engineering section.~. Cracks will have ~ to be .01'? 'or greater in width before changes will be~ recorded.-.
: 4. What are the criteriaiusedito determine the structural ~' integrity of:
the spent fuel pool?-
Procedure 2306.010 provides 11mits which. represents critoria:to; determine -appropriate-response based upon the! size of the crack. Any-significant crack- discovered would be evaluated on.a case by case
                      -basis considering the specific-location of the-crack-and-the load-
                      -bearingLcharacteristic of.the poolistructure at that.-location. : Other
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factors which may be considered . include the. calculated within the reinforcing steel and concrete; associated astresses llowable-stresses, and the amount of-reinforcing steel concrete cover. .Any detailed evaluation would probably referen'ce the original . evaluation and the documentation of=the initial-test results.-
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5 .'  Does your---inspection procedure include all of the'above information?
Our inspection procedure requires different responses lfor different-        ;
size cracks but does not specify-criteria to be used~when evaluating         !
11arger cracks.                                                                ;
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: 6. Ilow will-the five year frequency of inspection interval ensure the.       d structural integrity of the spent fuel pool? - Additional           _.
j justification is necesscry _ to extend the surveillance inspection -         j frequency to once per five years.- According to the_ inspection              !
records,. some new cracks or- spallings have been found every three          i
                      -years.                                                                     1
                                ~
The Proposed Technical Specification Change will require an _          .
inspection of spent fuel pool concrete surface at five year intervals        t
                      =instead of 18 month' intervals if no_ abnormal ~ degradation or:             '
indications of structural' distress are 4 detected. -                        ,
Thirteen inspections of the spent fuel pool concrete have been.            j conducted over.the'last eleven years without observance of abnormal          ;
                      ' degradation or. structural-distress.: This record provides-assurance-that the structural integrity of the' spent fuel pool is maintained.
The lack of any.nhnormal degradation or' indication of' structural-distress during-the past eleven years leads one to conclude that very little_ change is to be expected.-
With the exception of five-cracks observed during:the inspections            i
                      . conducted on March 20, 1985, all-cracks observed were smaller than
                       .01" wide (.01". width is the-limit provided by Procedure 2306.010)-
and most were.not structural related (such.as the_spalling reported in surface material-placed:over an expansion joint and cracks in:           j grout topping placed upon the: structural element.) All cracks              ,2 evaluated'have been found not to impact the structural integrity of.
the spent. fuel. pool._The five cracks found in 1985 which exceeded the screening limit width have not grown.
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